entry teams take first look at reactor head, polar crane tmi unit 2 ti and ep... · entry teams...

TMI UnU-2 Technical Information aExamination Program

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Entry Teams Take First Look at Reactor Head Polar Crane

The first close look at the Unit-2 reactor vessel head and the polar crane revealed expected rust but no visible damage according to members of the fifth containment entry team

The fifth entry into the Unit-2 containment conducted on December 11 by a team of 14 persons was devoted to visual inspection of the reactor head and polar crane additional radiation surveys and tests of decontamination procedures All tasks further photographic surveys of the containment interior Results from

the radiation surveys and decontamination tests are expected to be reported in a later issue of the TIampEP Update

Gregory R Eidam a TIO project engineer who participated in the entry repoted that the crane cables and hoole were rusty but appeared to be structurally sound One section of copper conductor from the crane was found to have fallen to the 347-foot floor level A more detailed examination of the polar crane including motors and auxiliary

equipment is tentativeiy planned for the seventh containment entry to be conducted in early March

Other team members reported that the area around the top of the reactor vessel appeared to be rusty Water was found in the north neutron shield tanks the south tanks were dry

Four persons from GPU companies were occupied for more than an hour taking additional radiation surveys on the 30S-foot floor level examing floor penetrations for future sump sampling aiuI checking locations for television cameras scheduled for installation during the sixth containment entry (see article in this issue)

Continued on Page 2

View from the top of the D-ring looldng down at the steam senerator (left) and the reactor coolant pump (right) Most of the exposed metal surfaces show little sign of corrosion

Exposed metal parts on the control panel for the auxiliary fuel handling bridge are extensively corroded Plastic buttons and control handles are partially melted

TIO Engineer Participates in Fifth Entry

Entry Team Continued from page 1

On the 347-foot floor level other team members tested gross decontamination methods to determine the most effective techniques The tests included water flushing at low pressure water flushing at high pressure decontamination Soiltion with abrasive scrubbing and a lowshypressure flusb strong decontamination

Gregory R Eidam a Technical Integration Office Project engineer helped inspect the Unit-2 polar crane during the fifth containment entry conducted on December I L

Eidam was the project engineer for the original in5tal1ation and refurbishment efforts for the polar

solution with low-pressure flush and a strippable coating The temperature of aU decontamination fluids was I 50degF

Among the entry team members was John Collins deputy program director of the Nuclear Regulatory Commissions (NRC) TMI Site Office Collins left TMI recently to take another NRC post with the Office of Inspection and Enforcement Region 4 in Texas

crale at the Loss-of-Fluid-Test (LOF1) Facility at th~ Department of Energys Idaho National Engineering Laboratory

We took the stairs up (from the 347-foot floor level) and climbed the crane access ladder between the two crane box beams Eidam said We

2

The TIampEP Update is issued by tbe EGlG Idaho lru Technical integration Offlee Document Couirol Center F 1 Kocsis maaaer under Department of Energy COBtNet No DEmiddotA07middot 76ID01S70 PO Box 88 Middletown PA 17057 Telephone 17-948-1010 or ITS 590middot1020

The TIampEP Update Is specifically designed to highllaht data and informadom obtained as part of tbe TMImiddotl Technical Information and Ewninatlon Program fIlampEP As space pennin the TIampEP Update may feature certain TMImiddotrelated information that though IUlt part of tbe 11ampEP would be of general Interest to the scientific community

WW Bixby is manager of tbe OOE-TMI Site Office HM Burton Is manager of the Technical Inteandon Office nM Grigg is IlIanaaing editr of the TIampEP Update GR Ikown is associate editor

took radiation readings and did a visual inspection The crane iooked rusty as were the couplings and the rails It appeared to be in structurally good condition

Eidam remarked that one section of copper conductor (bus bar) from the crane had fallen to the 347-foot level floor

Before climbing to the polar crane Eidam helped photograph conditions inside the containment He watched as part of the buddy-system plan when two other team members climbed down to inspect the top of the reactor vesseL

According to Harold Burton Manager of the TIO refurbishment of the Unit-2 polar crane is an extremely important activity of the TIampEP It represents a critieal path activity to early examination of the reactor cor~ and removal of the reactor vessel head both key recovery program milestones stated Burton

Eidam is scheduled to join the seventh containment entry team in late February for more extensive mechanical and electrical inspections of the crane and its components

Fourth Entry on Videotape

Twelve engineerS and technicians working in three shifts over a threeshyhourmiddotand-fortymiddotmlnute ~eriod filmed an hour of videotape footage inside Unit-2 as part of the reactor building damage ruessrnem during the fourth containment entry They supplemented the videotape by taking 71 stiU photographs

The November 13 videotape included O minutes of filming at the 305-foot floor lvel and 40 minutes at the 347-foot floor level The tape was later edited to 20 minutes and narration was added

The other utivities by team members on the 347-foot floor level included moviI~ the auciliary fuel handiing bndge lr easier access to a ladder leading to the reI r Y~ssel

head ara testing decotnina+ion methods a conducting ra~iologicaJ surveys

On the 05middotfoot level gamma readings ranged from 200 milIirem per hour (mremhr) in the northeast section of the containment to 3800 mremhr 3t the B cere flood tank piping Gamma readings on the 347-foot level ralged from 100 mremhr at the rap of the east Dring to 1000 mremhr at a floor drain and 1500 mremhr at ab(lu~ one meter into the west Dring

Smear sampies taken on the

30Smiddotfoot level as part of testing decontamination methods yielded the preliminary result shown in Table I

A scrape sample taken outside the decontamination nethods ~est area yielded preHlJIinary readings of 34 x 10-1 microcurie JJCi of ce~ium-134 and 24 J( 101 Ci of cesmm-137 A scrape sample from the test area following decontamination testing showed 50 x 10-2 )lCi of cesium-i34 and 36 x 10-1 )lCi of cesium-D7

A paint chip found on the floor at the 347-foot level had results of 16 x 10-2 )lCi of cesium-134 ll x 10-1 -lCi of cesium-137 and 48 x 10-3 )lei of strontiummiddot90 The chip is believed to be from the containment building dome

Continued on Page 4

T~ fourth entry was videotaped using a camera installed in containment penetration 626 Thls penetration was also used for visual examination of the containment interior a1d drawing reactor building Iiir satIples prior to the fIrst entry (see TIampEP Update of April 15 1980)

3

Fourtb Entry Continued from page 3

Table 1 Preliminary Analyses of Smears Taken on the lOS-Foot Level (in microcuries)

Treatment Sample No Cesium-l34 Cesium-37 Strondwn-90

Before decontamination 1 17EO plusmn 76E-3 12El plusmn 19E-2 23E-l plusmn 5117o 2 13EO + 66E-3 89EO + 16E-2 57E-l + SOlo

After demineralized 3 18E-2 plusmn 31E4- 14E-l plusmn 16E-4 52poundmiddot3 plusmn SOle water wash 4 26E-2 + 31E-4 19E-1 + 89E-4 14E-2 + SOle

After Radiac wash 5 18E-3 plusmn 2E-4 58E-2 plusmn 49E-4 56Emiddot3 plusmn SOle 6 38Emiddot3 + 14E-4 28Emiddot2 + 34E-4 71E-4 + 5

After Radiac scrub 7 8SEmiddot3 plusmn 21Emiddot 63Emiddot2 plusmn 5E-4 33Emiddot3 plusmn 50e 8 51Emiddot) + 16E4 36Emiddot2 + 39E-4 12Emiddot3 + 5011

Accumulation of boron crystals is evident around the base of the incore instrumentation seal table Corrosion is visible on the exposed metai surfaces

4

FJ Kocsis III TIO Information and Records Manager uses a computer tcrminal to relay TMI data to nuclcar utilities The terminal is part of the Nuclear NOTEPAD computer conferencing system

TIO Relays Data to Nuclear Utilities

A computer conferencing system is helping the TIO disseminate information to nuclear utilities about activities at TMI Unit-2

Nuclear NOTEPAD formerly known just as NOTEPAD offers computer conferencing among 62 nuclear utilities with operating or construction licenses the Nuclear Safety Analysis Center (NSAC) Institute of Nuclear Power Operations (INPO) and the TlO at Three Mile Island via either printout or video display terminals

Nuclear NOTEPAD users can receive from TIO the results from containment entries pertineut news stories about TMI activities and news releases from the GPU Public Affairs Office said Frank J Kocsis III TIO Information and Records Manager

As more reports and data about the TMI-2 recovery become available we will make announcements on NOTEPAD so that interested nuclear utilities may request it Kocsis said

Kocsis and Ronald Simard Assistant Director for Inforshymation and Data Services at NSAC set up the TMI NOTEPAD operation nine months ago NSAC and INPO jointly found NOTEPAD INFOMEDIA Corporation of Palo Alto California operates the computer conferencing system

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laquoNOTEPAD bas been used extensively to share expertise amoDi the nuclear utilities and gain information about Nuclear Regulatory Commission orders for design and operating changes in nuclear plants Kocsis said

NOTEPAD was organized in August 1979 after the Kemeny Commission criticized the lack of information being shared among nuclear utilities

The value of NOTEPAD officials said was demonstrated in February 1980 when Florida Power Corporations Crystal River Plant experienced problems and information sharing helped rectify the situatior

Cameras Installed in Unit2

Technicians have instaiied eight black-and-white television cameras inside Unit-2 to provide continuous visual monitoring of conditions inside the containment building Videotaping equipment included as part of thl system will allow making visual records of future events within the containment and will assist the TIO in documenting damage within the reactor buildini

The installation performed as part of the sixth containment entry on February 3rd and 5th included placement of four cameras each for overlapgting coverage on the 30S- and 347-foot levels of the building Technicians transported the cameras into the containment on the fllSt day of the entry and installed them on tbe second day

The night-vision cameras dubbed moon landers because of the white environmental housings atop tripods are linked to control consoles in the Unit-2 control room and the entry command center

Each camera has azoom lens with a one-billion-to-one dynamic range so that they will operate in extremely low light levels according to James W Mock the TIO project engineer who worked with General Public Utilities Corporation OD the installation Auxiliary lights can be attached to the cameras if necessary

The camera housings include windshield wipers to remove condensation that accumulates in the high humidity of the containment Each housing also has positions both inside and outside for attaching radiation dosimeters

Mock explained that for camera control from the consoles each camera unit has redundant receivers for remote operation of lats zooming panning and tilting Cables especially manufactured for the project carry the signals from the containment to the monitor screens on each console Operators at t1ie console an sec

ttansmissions from each camera and select a desired view for recording on videotape

Krypton-85 Venting Final Results

Final results of effluent monitoring done during the two-week venting of krypton-8S from the Unit-l containment showed tbat about 44132 Curies were released Ttle venting occurred from June 28 to July 11 1980 and was described in the TlampEP Update October 29 1980

Analyses indicated the reactor building originally contained about 44600 Curies of krypton In addition the project vented an estimated 13 Curies of tritium S5 x (0-6 Cuies of cesium-137and 572 x 10-9 Curies of strontium-90

Radiological monitoring by the General Public Utilities Corporation and the Environmental Protection Agency confirmed that detectable offsite releases of radioactive material were wen within the technical specifications set for venting by tbe Nuclear Regulatory Commission (NRC)

Since July the utility has vented about 100 Curies of krypton-IS a montb which is permissible within NRC guidelines The releases are usually made before entries into the containment buildinS

GEND Group Hosts First International Seminar

More than 100 persons from 21 countries learned about the PfOl1ess of the TMI Unit-l resarcb effort and plans for future work duriq a two-day seminar in Wasbinaton DC

The seminar hosted by the OEND group -- General Public Utilities Corporation Electric Power Raearch

6

Institute United States Nuclear Regulatory Commission and United States Department of Energy -- was the first directed to an international audience

The emphasis of the presentations was the plans for carrying out research programs and selected results to date in three areas -- instrumentation and electrical survivability decontamishynation and dose reduction and radioactive waste processing said Willis W Bixby DOE Site Manager atTMI

The GEND iIOUp sponsors the Three Mile Island Technical Information and Examination Program to obtain valuable ieneric information from the Unit-2 acciderlt

The November 21 and 22 seminar Bixby said included presentations on nine major task areas

bull Instrumentation and electrical survabUity

bull FISsion product transport and deposition

bull Decontamination and dose reduction

bull Radioactive waste handling bull Data bank

bull Mechanical component survivability

bull Early core damage assessment

bull Core deposition studies

bull Fuel and core component examination program

Participants also had the opportunity to watcb a 2O-minute narrated color vi_tape of the fourth enttl into the UDit-2 containment

The GEND p-oup plans to be quite flexible in workin with individual nations or orpnizations within nations Herbert Feinroth DOE director for the System and Safety Evaluation Division told the seminar SlJIICSIions for participation induded purchase of technical reports and direct involvement in development of nuclear waste disposal propams

Five countries - Germany Italy Spain Sweden and Taiwan - already have representatives at TMI to work with the utility Representatives from other countries pve positive responses to the possibility or participating but none have made committments as yet

Each government or organization at the meeting was encouraged to participate in a manner considered suitable to its need$ Bixby said

HP-RT-211 Analysis Results

Sandia National Laboratories has completed analysis of radiation detector HP-RT-211 which was removed from the containment building during the second entry (see TIampEP Update of October 29 1980) The major preliminary fmdings are

bull the total radiation dose estimate for the detector is lower than previous estimates

bull equipment haviq electrical connectors should be oriented so that the connector is shielded from direct spray or the coitnector shell should be potted to reduce the possibility of water and

contaminant intrusion and

bull with slight adjustment or modification some instruments may still provide correct and usable information despite partial failure

The cause of the instrument failure was confirmed to be a 163-ohm short circuit between the coDector and emitter of a 2N-3906 transistor which was part of the detector output circuit

Scannin electron microscope photographs showed a catastrophic punch-through between the collector and emitter Scientists postulated that the failure occurred when the containment buildina spray system actuated durin the TMl incident shorting the sisnaI and 600-volt pins in the backshell of rhe connector jl)inin the detector to ib cable (No other radiation detector failed in this manner)

Although the failur~ caused the instrument to indicate lowgt instnunent data recorded on a stripchan appear to be proportional to actual r~tion levels in the containment Efforts to

reconstruct the radiation proflle time history are continuing

Six transistors two pieces ofTeflon tubinJ and a buna nitrile 0 ring were removed from the detector for use in estimating the total gamma radiation dose Data collected by exposinl like devices to known radiation doses enabled scientists to estimate the total dose at the detector location within the containment to be between 076 and 36 rads

Gamma spectroscopy and radiochemical analysis of the outside detector surfaces indicated the presence of cesium and strontium contaminants but no transuranics (to the minimum detectable limits of the instruments used) The top horizontal surface had cesium-134 and cesium-137 pmma levels of 0048 and 0305 microcurL per square centimeter respectively The levels on the sides and bottom were lowlaquo by a factor of four Beta-gamma film proftles of the contaminant cli5tributions showed localized hotspot The 0 rin seal prevented ClDtamioants from enterin the inside of the detector

I

A major rage in the recovery and (leanup of the damaged TMI-2 reactor began in July with tPsting of an ion exshychange water treatment process known as the Submerged Demineralizer SYBtem (SDS) The 5DS will process 100000 gallons of coolant in the reacshytor coolant system and 600000 gallons of more highly contaminated water from the bseruent of the Unit 2 containment building Together with

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Submerged Demineralizer Syst~em Processes Contaminated Water

TMI Unit-2 Technical Information ampExamInation Program

the containment entry program (see arshyticle this issue) the cleanup of this water is OIle of the two major ongoing projects of the recover program

Removal of the contaminated water from the reactor building will signiflC8Jltly reduce the levels of direct and mobile airborne radiation present in the building The water is a source of direct radiation to plant personnel who must go into the reactor building dueshy

ing containment entries to maintain plant systems The removal of CCnshytaminated water which entered the reactor buildinB through an open relief valve during the accident more than two and a haIf years alo is a necessary st~ in the recovery effort

The 8DS is an ion exchange process similar to the BPICOR n system used earlier in the recovery effort to treat

Continued )n Page 2

TMI-2 SUBMERGED DEMINERALIZER UNIT 2

CONTAINMENT BLDG

PROCESSED WATBI STORAGE TANK

SYSTEM

Demineralizer System Continued from

500000 galloJllt of water in the less contaminated auxiliary building (see July 311980 Update) The SOS differs from the EPlCOR II in two major ways First the SOS operates under water in the Unit 2 spent fuel pool adshyjacent to the reactor building This underwater operation protects plant workers from the high radiation levels

Second the SOS uses an inorganic material called zeolite rathe than the predominantly organic resins used in EPICOR n to absorb the fission proshyducts from the water The SOS zeolite is composed of 40 percent Linde ionsiv zeolite-A-51 and 60 percent Ionsiv zeolite-IB-96 The inorganic zeolite can accommodate loadings in excess of 20000 curies per cubic foot while resins in the EPICOR II system norshymally accomodate loadings less than an average of 40 curies per cubic foot The ion exchange process in the SDS effecshytively removes more than 99 percent of the fission products primarily cesium and strontium from the contaminated water The ion exchange media are exshypected to produce a decontamination factor in excess of 30000 for cesium and 250 for strontium Tritium a flSshysion product also present in the water can not be flltered out because of it~ structural similarity to the hydrogen component of the water molecule

Radioactive water from th baseshyment of the reactor building is being pumped into the SOS in the spent fuei pool by means of a SUCtiOD pump floating on the surface of the CODshytaminated water (see accompanying figure) The water passes through preliminary ruters and on to the zeolite resin canisters After it passes through the zeolite canisters the water can be stored in tanks or can be processed further with the EPICOR II system The further processina through EPICOR II is expected to produce an average decontamination factor in exshycess of 100 for cesium and strontium

SDS processing of contaminated water generates radioactive waste in the form of filters and ion exchange resins laden with radioactive concenshytrates This waste will be temporarily stored in the fuel poOl a4jacent to the demineralizer ~em orin specially constructed containers on site The

Department of Energy (DOE) plans to program as planned can proceed with ship the SDS resins to DOE facilities little risk to plant personnel or the for research development and testina public NRC approval of the SOS purposes allowed plant technicians to begin test

The pr~sed water from the SOS processing of water through the still contains concentratioJllt of tritium system Approximately 1SO000gallons in excess of 08 microcuries (pCi) per of less heavily contamjnated water milliliter Until the Nuclear Regulatory from the auxiliary building were proshyCommission (NRC) approves final cessed during the summer of 1981 and disposition of this water it will be processing of the reactor building stored in various tanks on oile Potenshy sump water began in September tial on-site use of the water may inshy By the end of the third week in Ocshyclude pumping it back into the reactor tober the 80s system had processed building to protect workers from approximately 123000 gallons of reacshyresidual radiation on the buildings tor building sump water The system basement floor and using the water in processing rate is about 5 gallons of decontamination activities and in water per mmw Recovery program various plant systems Most of the estimates indicate that it will take water to be processed will be stored in about four to five months to process two specially constructed SOOOOO the contaminated water in the TMI gallon tanks on site Unit 2 containment building

Actual implementation of SOS The 8DS cost $11 million to desisn testing was not possible until the third and build Its use will be a aignificant week of June when the NRC approved step toward the cleanup of the damagshyits use Approval was contingent upon ed TMl Unit 2 nuclear plant SDS the conduct of an NRC study of the enshy operation will also provide generic inshyviionmental consequences of the entire formation to the nuclear industry recovery program This study now regarding processing of high specific completed concluded that the cleanup activity liquids

First Multilevel Sample Taken EOampG engineers developd a unique bull Minimizes losses of floccu1ant durshy

Ull -lmel sampling device to obtain ing sampling by rapid sample acshyrepresentative liquid and sludge quisition samples from the 600000 gallons of bull Minimizes losses of entrained gas inhighly contaminated water in the the sample T1lmiddot2 containment building baseshyment The device called Water and bull Permits exact sample locations to be

determined relative to the basementSludge Sample Device (WSSD) was floordesigned to obtain eight simultaneous

ISO-milliliter samples at four different bull Provides mown sample volumes levels This technique will allow scienshy

bull Ensures that outside of sample botshytists and -engineers to determine the exshytle rmutins contaminationmiddotfree by tent of stratification and floeculant usinl watertight bottle housings dispersal patterns in the eigbt and a

half feet of water in the containment bull Allows immediate visual observashybasement tion of the sample

The lightweight aluminum device In addition Iiamphtweiampht desisn of thewas designed for easy operation under WSSD permits operation by one inmiddot adverse conditions inside the Containshy dividual ment building Unique features of the The lower portion of the WSSD isWSSD include the foDowmg shown in the accompanying bull Acquires eisht simultaneous photOgraph Evacuated sample bottles

samples at four levels two near the are placed septum down into the shield liquid surface two at the mid-Jevcl base to eoaaaeWith an O-ring to form two near middotthemiddotmiddot bottom and two the lower watertiaht sealbullbullInstallation sIudse~ples of tbe shield cap Over tJJeshield base

bull Minimi_stlatificaiiamiddot~ ~ance - eontinUed onPtiP 3

Sample Taken Continued from Page 2 engages the outer shield base O-ring to complete the watertight anticon~

tamination seal of the containment housing around each bottle The shield caps are securely locked into position by a fast-acting shieId cap bar ratchet assembly The locking bar ratchet assembly permits rapid unlocking and removal of the shield caps to minimize personnel operating time and radiation exposures The sludge sample isolation cup at the base of the WSSD traps an area of sludge on the basement floor and maintains the actuating needle sucshytion point as close to the floor as possishyble in order to ensure representative sampling

After the WSSD is lowered into the proper position in the containment basement an enabling pin is removed and sampie acquisition is initiated by plunger action This action drives the actuating needles through the sample bottle septums causing liquid or sludge samples to be rapidly forcedinshyto the evacuated bottles When the WSSD is raised the bottles retract from the needles and the self-sealing septum prevents any loss of sample material The WSSD is raised from the basement to the 305-foot elevation and technicians remove the sJield caps This exposes the sample bottles which

Lower Portlou of tile Water ad SlImp SampUaamp Dmce

Table 1 nnmiddot reactor building basemeut water sample IlIUIIyses lI5ultsS

Sample Nqmber 1 3 6 I

Nadide SMn 6OCo 90sr 90sr l06Ru 12SSb 1191 134es 137es 144Ce

(ltClm)

NOb gt6E-04 SO plusmn O2E-rOO 54 t OSE+OO

NO gt3E-02 55 plusmn 01E-06 US plusmn OOlE+Ol 143 plusmn 001pound+02

NO

(ltCllmJ)

NO gt3E-03 54 plusmn O2E-rOO 52 t 05E+00

NO gt3pound-02 54 t O1E-OS 184 plusmn 001E+Ol 142 plusmn 00IE+02

NO

(pCilml)

NO gt2E-03 52 plusmn O2E+OO 51 plusmn 05E+00

NO gt3pound-02 38 plusmn 05E(16 186 t 00IE+01 143 t OOIE+02

NO

Slany 4tWllIIl)

gt2E-04 gtIIE-04

NA NA

gt4E)4 gtSE-m

NA 187 plusmn OOIE+Ol 144 plusmn 00IE+02 gt8E-03

Sgpenate 4tW1IIl)

NAf NA NA

S3 plusmn OSE+OO NA NA

25 plusmn OSE()6 NA NA NA

~ (jampCII1101lda)

NO 17 plusmn O2E+OI 8 plusmn 2E+02 78 plusmn 08pound+02

NO 45 t 02E+02

NA 179 plusmn 004pound+02 129 t OOIE+03 76 plusmn 068+01

(paIJ) (-atIIGHlls)

ltIE-02 lt1E-02 lt1pound-02 NA NA 88 plusmn O9EOl 4 plusmn lE-08 NA NA j plusmn 1amp07 NA Splusmn lE~ 22 plusmn 07B-04 NA NA 26 plusmn 05E-03 NA 2 plusmn 068-03

a Concentrations as of 6-1-81shyb NO = not detected c NA - iIot anaIy7ed

I

The prellmJaarJ polar eraue lDapectIOD was the tIrrit ill bull Iedes of btspeedOBS to detcmalae lbe paeral coJldidoa of tile crae ad to collcluct ovenill area damage usessmems ud radladoa lIIlVeys

Preliminary Inspection of Polar Crane Complete

A four-man team performed the preliminary inspection of the TMI-2 reactor building polar crane during containment entry 13 The inspection included opening and inspecting the drive train and main hoist gear boxes

Sample Taken Continued from Page 3 free of external surface cont2mination are loadoo into lead-shielded shipping containers ~ The WSSD was successfully used on ampay i4 1981 durbtg containment enshytryIO to obtain eight TMI-2 containshyment basement water samples The samples were shipped to the Idaho Nashytional Engineering Laboratory for

analysis and archiving Four samples were archived and the preliminary analytical results of the other four are shown in the accompanying table

Bach of the four samples analyzed was taken at Ii different level re1aIive to

the basement floot Sample 1 was

conducting motor winding resistance checks performing visual inspections of the motors internals through their inspection ports and conducting overall area damage assessments and radiation surveys This inspection was

taken at 84-34 inches above the floor sample 3 was taken at 47-34 inches sample 6 at 5-318 inches and sample 8 at the basement floor itself Sample 8 contained solids as well as liquid and both of these were analyzed in the study The table contains data from nuclide analyses conducted for the gamma emitters (cesium-I37 and -134) for the beta emitter (strontium-go) for the x-ray emitter (iodine-l29) and for fissile material In addidon the presence of ceriUin-l44 antimonY-1lS and cobalt-60 were observed and were quantitativelymiddot measuredwbcre possishyble All data gathered in these analyses are currently uncierloinB further detailshyect analysis

the flISt in a series of detailed inspecshytions to determine the general condishytion of the crane and to provide early assessments of which components may require replacement

The polar crane work is an essential part of the TMI-2 recovery and RampD efforts since the crane is required to remove missile shields and the reactor vessel head The two major areas of RampD interest include electrical and mechanical component survivahility The Technical Integration Offices Inshystrumentation and Electrical program ill focus its efforts on determing the survivability of such components as limit switches motors loadcells and control cabinets The Electric Power Research Institutes Mechanical Comshyponents program will focus its efforts on determining the survivability of such components as reduction gears cable drums and wire lape These efshyforts will not only provide the data necessary forGPU to determine the exshytent of reburbishment required but

will also contnbute v8iaabIe informashytion to ovCraJIwderstandina of the the reactor 1l1uk611amp enVitonmcdt dlllinlmiddotthe aCcident

TMI Containment Entry Highlights A total of eight successful containshy

ment entries have been completed since the last issue of the Update Following are highlights of the key tasks performshyed during these entries

Entry IS This entry was conducted over a twoshyday period February 3 and 4 198L Eight closed circuit TV cameras were installed decontamination tests and photographic surveys of damage were conducted on the 347-foot elevation (see photo) radiation surveys were made and various samples of paint chips and other materia] were obtained from the 347-foot elevation

Jtintry 7 This entry was conducted over a threeshyday period March 17 18 and 19 1981 Three onemiddotliter samples and one 150-milliIitr sample of the water in the containment building basement were obtained using a rota-flex pump A zeolite column was installed and operated to obtain five gallons of proshycessed effluent from the basement

water for the Submerged Demineralshyizemiddot System (SDS) development data (s~e SDS article this issue) Detailed adiation and photographic surveys were conducted in the in-cCre inshystrumentation tunnel area to support the sump surface suction plan for the SOS In addition the first radiation surveys were conducted at tlte top of the CRDM service structure (see photo)

Entry 8 This entry was conducted on April 8 1981 A photographic survey Etnda general reconnaissance of the area at the 305-foot elevation open stairwell were conducted Closed circuit TV cameras numbers 4 and 7 which were installed in entry 6 were repositioned (see photo) and the power soune for camera number 7 was changed

Entry 9 This entry was conducted on April 30 1981 The cover of penetration lR-S61 was removed in preparation for entry 10 decontamination testing GPUs

SDS sump pump was inst31Ied through the open stairwell and a photographic history of the pump installation was made A photographic survey of elecshytrical penetrations R-S04 and R-509 wa~ made for the Instrumentation and Electrical program A radiation survey of zeolite resin columns used in entry 7 was conducted The scaffolding used to install the closed circuit TV cameras in entry 6 was dismantled

Eutry 10 This entry was conducted on May 14 1981 Safety equipment was installed on accessible portions of the polar crane Radiation and smear surveys were conducted on the control rod drive mechanism service stll1cture inshyternals Entry team members obtained six water and two sludge samples from the containment basement using EGampGs Water and Sludge Samplins Device (see article this issue) They also performed the rust large-scale

Continued on Page 6

Teetmiclaus emeriag the TMImiddot2 containment bWldJDg In ODe of bull series of IIIIIlQJed Imtria into tile buiJdiag

(GPU Nuclear Photo by Don Shoemaker)

5

Entry Highligbts Continued from Page 5

decontamination experiment on the 305-foot elevation using an initial spray mist and a combination of low pressure and bigh pressure sprays In arldition a post-decontamination exshyperiment cleanup was performed

Entry 11 This entry was conducted on May 28 1981 Areas where large-scale deconshytamination experiments were conshyducted during entry 10 were protected from recontamination by using conshytamination control areas and promiddot cedures (see photo) Entry team members completed installation of polar crane safety equipmellt transfershyred a portable gamma spectrometer inshyto the reactor building and ebtained three floor scans on 305-fo01 elevation which included three area spectra emd three background spectra Technicians replaced radiation monitor HP-R-213 on the 347-foot elevation with a new instrument and replaced the GAIshytronics paging telephones on the 305- and 347-foot elevations with llew ones The team members also performshyed radiation and photographic surveys of the pilet-operated relief valve and other general areas within the east D-ring (or biological shield) and censhynected SDS hoses to the R-626 penetrashytien

Entry U This entry was conducted on June 25 1981 Closed circuit TV camera number 4 was replaced and the conshynectors cn camera number 7 were repaired Entry team members pershyformed maintenance and medification tasks en lighting panel LPR-3A and the GAI-treDics telephone system they installed temporary lighting in the enclosed stairwell and they performed smear surveys on the walls at the 305- and 347-foot elevations Loose samples of peeling paint were obtained at the 305-foot elevation near core flood tank B at an electrical box at the 347-foot elevation and from the conshytainment dome on the floor north of the open stairwell at the 347-foet elevashytion

Continued on Page 8

6

Ooseo ircult television amera number 4 at open st~n on tbe 305-foot elevation (TID Photo Entry 8)

Physics techulcbm performingthe first radiation survey on the lOp of tbe coatrol rod drive meduudsm service sbIletIIft (TID Photo Entry 7)

7

Technidans rltdlOVe outer set of protective 8boe covers at eootaDduatioD COD~~ area OD the J85foot elevation (TIO Photo EntTy 11)

Entry Highlights Continued from Page 7

Entry 13 This entry was conducted on July 1 1981 This entry was made to perform radiation surveys and to complete the polar crane inspection which had to be aborted during entry 12 due to proshyblems with personnel airlock no 2

Entry 14 This entry was conducted on July 23 1981 Closed circuit TV camera number 2 was replaced and connectors on camera number 8 were repaired Team members obtained a 1 SO-milliliter sample of the water under personnei airlock number 1 and a samshyple of the white crystal accumulatiun on the floor of the 347-foot elevation by the in-core instrumentation seal table Water samples from the neutron shield tanks could not be obtained because the tanks are empty Photographic surveys were taken of the air coolers and some selected inshystruments- Beta and gamma radiation

and mtear suveys were conductJed on the reactor vessel service structure and the refueling pool floor Entry team members removed core flood tank transducels CFI-PT4 and eF2-L1r4 for analysis and installed a continuous air monitor and an area radiation monitor In addition Radiologic=1 Engineer DeUa Loggia became thle flISt woman to enter the TMI-2 COltainshyment since the accident

Entry 15 This entry was conducted on August 17 1981 Spectra from scans of the floor on the 305-foot elevation were obtained by gamma spectrometry Overhead beta and gamma and S1Deuroar

surveys on core flood tanks JA and IB and on platforms on the east side ofthe reactor buildinq were also obtained In addition a remote radiaion survey of the deep end ofthe refuel pool a smear survey on the mezzanine and a survey around the open stairwell were also obshytained One entry team inspated the stealn generator cleaning line and obshytained severa photographs of the area

8

Another team replaced closed circuit TV camera number 8 with a new camera box and installed new wires and a control box on camera number S Reactor building nitrogen pressure alarm switch NM-P8-14S4 was replac ed and flow transmitter MU-IO-FTI was removed The last entry team pershyformed air cool~ inspections and took photographs of the motors They also obtained some thermocouple readings

Entry 16 This entry was conducted on September 24 1981 Two teams photographed various penetrations and inventoried the defueling tools in the building One of the teams inshyspected the air cooler fan motors removed three fan motor covers and obtained one resistance temperature device reading The third team obtainshyed a Slunp water sludge sample at the open staintdl using EGampGs Water

and SIndge Samplingmiddot Device (see arti shycle this isSue) The fourth team pershyformed containment charaCterization

suJvCys on the 347-fobt elevanon bull

Department of Energy Ships EPICOR n Resin Canister To Research Facility

Al EPICOR II resin canister from a contaminated-water treatment system at TMI-2 was shipped to Battelle Colshyumbus Labs (BCL) in West Jefferson Ohio on May 19 1981 The Departshyment of Energy (DOE) coordinated the ~hipment of the resin canister to the Ohio research facility

The canister a prefilter referred to as the PF-16 liner is one of a total of more than SO highly loaded EPICOR II liners used in processing contaminated water in the auxiliary building at the damaged Unit 2 reactor DOE will sponsor research to determine the con-

wading the EPICOR n resiD cauIstrr for shippinggt

dition of the highly loaded rfsins and liners after they have been stored for long periods The selected liner was usshyIOd March 3 and 4 1980 to process 8250 gallons of contaminated water from the auxiliary building The PF-Hi is one of the most highly radioactive resin liners used in the EPICOR II system with a loading of approximately 1300 cuties of cesium-137 and strontium-90

Researchers at BCL haive betlln a variety of tests on the liner These tests include resin sampling analysis gas and liquid sampling analysis visual exshyamination of the liner and various other studies of its chemical and radiological makeup The tests will continue over several months enalytica1 results on these studies will be published in future issues of the Upshydate as data become available

BCL analysis of the PFmiddot16liner will contribute to the development of technology for storing processing and disposing of contaminated resin liners Some specific goals of the program inshyclude acquisition of deJa for

bull Developing short-term storage reshyquirements for such liners

bull Developing storage canisters and disposal requirements for permashynent burial

bull Determining the effects of longshyterm storage 011 the--e resins and canisters

bull Developing other options for proshycessing the resins

The PF-161iner was sbipped to Batshytelle in a high integrity roielded cask mounted on a low-boy tractor trailer (see photo) The liner is 48 inches ~ diameter and 60 inches high and conshytains approximately 32 CUbic feet of ion exchange media It was shipped in a licensed type B cask 92 inches high and 85 inches in diameter The cask walls consist of two one-inch layers of steel separated by three and one ball inches of lead The cask was designed to resist extreme environmental stresses such as fU1 and immersion in water

Although the PF-16 liner was the fUst bilJhly loaded resin canist= to leave the island since the 1979 accident General Public Utilities (GPU) shipped 22 low level radioactive resin canisters from the EPlCOR II system to a burial site in Hanford Washington between April 22 and June 28 1981 The last canister shipment arrived in Hanford on June 30 1981 The radiation levels of these shipments were lower than those of routine low level wastes from other nuclear power plants

TMI-2 GEND Reports Available to the Public In the continuing effort to distribute

information about the TMI-2 cleanup and recovery effort to th- nuclear inshydustry twelve reports on various aspects of the Technical Information and Examination Programs (TI~P) have been published A brief descripshytion of each of these reports is offered below along with the formal report tishytle its number and its date of publicashytion These reports are available from the Technical Information Center US Department of Energy Oak Ridge Tennessee 37830

GEND Planning Report GEND 001 ublished October 1980 The report describes overall planlt for the Technical Information and Examinashytion Programs as established by the GEND group General Public Utilities the Electric Power Research Institute tbe Nuclear Regulatory Comshymission and the Department of Energy

Facility Decontamination Technology Workshop November 27-29 1979 Hershey Pennsylvania GEND 002 published October 1980 This report provides a record of decontamination and dose reduction activities at other facilities The report is in tne form of published proceedings of the deconshytamination technology workshop

TMI-2 Injormation and Examination Program Technical Integration Office Annual Report GEND 003 published February 1981 The annual progress report discusses activities conducted under the DOE portion of the TIampEP during FY-1980

Interim Status Report on Personnel Dosimetry GEND 004 published June 1981 Dosimetry studies documented in this report surveyed available dosimeter systems set up a prototype system and compared the prototype with the commercial systems

Characterization oj the Three Mile bland Unit 2 Reactor Building Atshymosphere Prior to tke Reactor Building Purge GEND OOS published May 1980 Samples of the TMI--2con--Ieport discusseS ~oltheconcept woment atmosphere taken prior to the procCdure$aQ4 toOlliigde5crlptioils kryptonSS venting were analyzed for presented inmiddotmiddot themiddot Piiase I repO-t

radionuclide concentrations and for gaseous molecular components The sampling procedures analysis methods and results are summarized in this report

Three Mile Island Unit 2middotCore Status Summary A Basis jor Tool Developshyment jor Reactor Disassembly and DejueJing GEND 007 published May 1981 The report summarizes TMI-2 core damage analytical assessments performed by reconstructing the seshyquence of events by estimating the amOlIlt of hydrogen generation and by evaluating the amount of ftssion products released

Report on Citizens Radiation Monitorshying Program GEND 008 published July 1981 The Citizens Radiation Monitoring Program developed a system for citizens to independently measure radiation levels in and around their communities The report describes the program and its results

Measurements of 1-119 and Radioacshytive Particulate Concentrotions in the TMI-2 Containment Atmosphere Durshying and After the Venting OEND 009 published April 1981 The report discusses the equilibrium concentration and species distnoution dming and after the reactor building krypton-8S venting Concentrations of iodine-129 krypton-SS cesium-134 cesium-137 and strontium-90 were measured durshying the venting Operation and are reported here

In- Vessel Inspection Before Head Removal (Conceptual Development) GEND 010 PHASE I published AUgJJst 1981 1JUs first phase of a three-part report deals with conceptual development of the core inspection project Concepts are described for inshyternal inspection of the reactor vessel and fuel assemblies prior to removal of the reactor vessel head

In- Vessel Inspection Btfore Head Removal (Tooling and Systems Design) QEJID 010 PHASE II published July 1981 ThiSmiddot plUse II

Preliminary procedures for beginning the work are also presented

Canistu Design Considerations for Packaging TMI-2 DflmIlged Fuel and Debris GEND 011 published October 1981 This document reviews reshyquirements and provides design conshycepts for a standardized canister for packaging damaged fuel and core debris

TMJ-2 Reactor Building Purge-Kr-85 Venting GEND 013 published March 1981 A comprehensive technical report is presented on the total effort involved in deconshytaminating the reactor building atshymosphere by venting the contained krypton-8S to the environment

Accountability Study for TMJ-2 Fuel GEND 016 published May 1981 The Accountability Study considers proshyblems of identifying measuring and accounting for TMI-2 fuel in its preshysent condition and as it is removed from the core and examined The study identifies methods which will provide a material balance equal to the preshyaccident balance

Technical Integration Office Reorganized

The Technical Integration Office at DOEs Three Mile Island Site Office has beeit reurganized to accomodate the expanded research effort of the program over the next several years The program has been separated into two major areas of aCtivity the Data AcqUisition Programand the Waste Immobilization and Reactor Evaluashyti6nProgram Both ~f these plogouns fall Unaertbe ovemll title ofthe TMI-2 TCchnjealinfonnadon Bud Examinashytion PrognuDs orTIampEP ~a ACquisition Program activities

williriclUde the COnfiguration andmiddot bullmiddotIgtcJciDnenteontro( Center the inshy

strumentatiOn atlclE1CctiACalmiddotPJograin

the Radiation and Environment Proshygram the Off-Site Core Examination Program and the Radwast~

Technology Dlvelopment Program The Waste Immobilization Program will conduct zeolite and resin disposishytion studies and the Reactor Evaluashytion Program will conduct core damage assessment reactor disasshysembly studies and fuel and core storage and disposal research and development The reorganization became effective October 1 1981 with the start of the new ftscal year

Tbe TIampIP Update is issued by the EGampG Idaho Inc Configuration and Document Control C~Dter at Three Mile Island under contract DE-AM07-761D01570 to tlgte Department of Energy PO Box 88 Middletown PA 17057 Telephone 717 948-1050 or FrS 590-1050

Aullu)t5 S A Elllniler T J Lewl OOEmiddotTMI Site Offipounde Manair W W Bixby EGampG TMImiddot~ Programs DMslon MaMger S M Burton Conrlgullltlon Ind Document Conlrol Center SlIpervlsor bullbullbullbullbullbullbullF I Meltzer

EGAG (dalto bubullbull PO Boll U MichDrwWD FA 17057

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Exposed metal parts on the control panel for the auxiliary fuel handling bridge are extensively corroded Plastic buttons and control handles are partially melted

TIO Engineer Participates in Fifth Entry

Entry Team Continued from page 1

On the 347-foot floor level other team members tested gross decontamination methods to determine the most effective techniques The tests included water flushing at low pressure water flushing at high pressure decontamination Soiltion with abrasive scrubbing and a lowshypressure flusb strong decontamination

Gregory R Eidam a Technical Integration Office Project engineer helped inspect the Unit-2 polar crane during the fifth containment entry conducted on December I L

Eidam was the project engineer for the original in5tal1ation and refurbishment efforts for the polar

solution with low-pressure flush and a strippable coating The temperature of aU decontamination fluids was I 50degF

Among the entry team members was John Collins deputy program director of the Nuclear Regulatory Commissions (NRC) TMI Site Office Collins left TMI recently to take another NRC post with the Office of Inspection and Enforcement Region 4 in Texas

crale at the Loss-of-Fluid-Test (LOF1) Facility at th~ Department of Energys Idaho National Engineering Laboratory

We took the stairs up (from the 347-foot floor level) and climbed the crane access ladder between the two crane box beams Eidam said We

2

The TIampEP Update is issued by tbe EGlG Idaho lru Technical integration Offlee Document Couirol Center F 1 Kocsis maaaer under Department of Energy COBtNet No DEmiddotA07middot 76ID01S70 PO Box 88 Middletown PA 17057 Telephone 17-948-1010 or ITS 590middot1020

The TIampEP Update Is specifically designed to highllaht data and informadom obtained as part of tbe TMImiddotl Technical Information and Ewninatlon Program fIlampEP As space pennin the TIampEP Update may feature certain TMImiddotrelated information that though IUlt part of tbe 11ampEP would be of general Interest to the scientific community

WW Bixby is manager of tbe OOE-TMI Site Office HM Burton Is manager of the Technical Inteandon Office nM Grigg is IlIanaaing editr of the TIampEP Update GR Ikown is associate editor

took radiation readings and did a visual inspection The crane iooked rusty as were the couplings and the rails It appeared to be in structurally good condition

Eidam remarked that one section of copper conductor (bus bar) from the crane had fallen to the 347-foot level floor

Before climbing to the polar crane Eidam helped photograph conditions inside the containment He watched as part of the buddy-system plan when two other team members climbed down to inspect the top of the reactor vesseL

According to Harold Burton Manager of the TIO refurbishment of the Unit-2 polar crane is an extremely important activity of the TIampEP It represents a critieal path activity to early examination of the reactor cor~ and removal of the reactor vessel head both key recovery program milestones stated Burton

Eidam is scheduled to join the seventh containment entry team in late February for more extensive mechanical and electrical inspections of the crane and its components











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entry teams take first look at reactor head, polar crane tmi unit 2 ti and ep... · entry teams...

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